• 대한기계학회논문집B
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• 제35권10호
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• pp.1089-1095
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• 2011

열전달 향상을 위한 방법으로 많이 사용되고 있는 마이크로 핀을 포함한 표면 위에서의 핵비등을 액상과 기상에서 질량 및 운동량, 에너지에 대한 지배 방정식을 풀어 수치해석을 수행하였다. 핵비등에서의 기포거동을 계산하기 위해 sharp-interface 레벨셋(level-set) 방법을 상변화 효과와 핀과 캐비티와 같은 잠긴 고체에서의 점착 조건 및 접촉각, 마이크로 액체층에서의 증발 열유속을 포함하도록 수정하였다. 핀과 캐비티를 포함한 표면에서의 기포 생성, 성장, 이탈에 대한 해석을 통하여 핀-캐비티 배열, 핀-핀 간격이 핵비등에서의 기포거동에 중요한 역할을 하는 것을 확인하였다.

• 대한기계학회논문집B
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• 제24권9호
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• pp.1239-1246
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• 2000

The objective of this work is to measure space and time resolved wall heat fluxes during nucleate pool boiling of R113/R11 mixtures using a microscale heater array in conjunction with a high speed CCD. The microscale heater array is constructed using VLSI techniques, and consists of 96 serpentine platinum resistance heaters on a transparent quartz substrate. Electronic feedback circuits are used to keep the temperature of each heater at a specified temperature and the variation in heating power required to keep the temperature constant is measured. Heat flux data around an isolated bubble are obtained with triggered CCD images. CCD images are obtained at a rate of 1000frames/second. The heat transfer variation vs. time on the heaters directly around the nucleation site is plotted and correlated with images of the bubble obtainedby using the high speed CCD. For both of the mixture(R11/R113) and pure system(pure R11, pure R113), the wall heat fluxes are presented and compared to find out the qualitative difference between pure and binary mixture nucleate boiling.

• Journal of Advanced Marine Engineering and Technology
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• 제40권4호
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• pp.275-281
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• 2016

본 연구에서는 전산유체역학(CFD)을 이용하여 저압에서의 과냉각 비등 현상에 대한 수치해석적 연구를 수행하였다. 과냉각 비등 현상을 시뮬레이션하기 위해서 벽비등 모델을 사용하였으며, 벽비등 모델은 기포 이탈 직경, 핵 사이트 밀도 그리고 기포 이탈 빈도로 구성된 하위모델을 필요로 한다. 전산유체역학 코드 CFX는 실험 자료에 근거한 기본 모델을 제공한다. 하지만 이러한 모델은 대부분 고압조건에서 개발되었기 때문에 저압조건에서는 잘 맞지 않는 것으로 보인다. 따라서 본 연구에서는 저압조건에서 과냉각 비등 현상에 대해서 CFD의 유효성을 검토하였다. 수치해석적 결과는 기존의 실험 결과와 비교하였다. 수치해석은 질량유속 $250{\sim}750kg/m^2s$, 열유속 $0.37{\sim}0.77MW/m^2$ 그리고 출구압력 0.11 MPa범위에서 수행되었다. 저압조건에서 개발된 상관식을 적용함으로써 수치해석의 정확성을 높일 수 있었다.

• 대한기계학회논문집B
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• 제32권2호
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• pp.125-132
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• 2008

The bubble dynamics and heat transfer associated with nucleate boiling in parallel microchannels is studied numerically by solving the equations governing conservation of mass, momentum and energy in the liquid and vapor phases. The liquid-vapor interface is tracked by a level set method which is modified to include the effects of phase change at the interface and contact angle at the wall. Also, the reversible flow observed during flow boiling in parallel microchannels has been investigated. Based on the numerical results, the effects of contact angle, wall superheat and the number of channels on the bubble growth and reversible flow are quantified.

• 한국유체기계학회 논문집
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• 제14권6호
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• pp.45-53
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• 2011

Multiphase lattice Boltzmann method (LBM) has been used to simulate the nucleate pool boiling directly. For the phase change model, the thermal model and the Stefan boundary condition were introduced to the isothermal LBM. The phase change model was validated by the bubble growth in a superheated liquid under no gravity. The bubble growth on and departure from a superheated wall has been simulated successfully. The preliminary results showed that the detail process of nucleate pool boiling was in good agreement with the experimental results.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2839-2846
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• 2021

In this study, experiments of downward-facing flow boiling were conducted to investigate material effects on CHF. Experiments were conducted using aluminum, copper, and carbon steel. It was found that different materials had different CHFs. Aluminum has the biggest CHF while copper has the lowest CHF for each mass flux. After experiment, surface wettability increased and surface became rougher, which was probably due to the oxidation process during nucleate boiling. The CHF difference is likely to be related to the surface wettability, roughness and thermal effusivity, which influences the bubble behavior and in turn affects CHF. Further studies are needed to determine which factor is dominant.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1241-1250
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• 2019

This study mainly focused on the neutronics modeling of bubbles in bubbly flow in boiling water reactors. The bubble, ring and homogenous models were used for radial void fraction distribution. Effect of the bubble and ring models on the infinite multiplication factor and two-group flux distribution was investigated by comparing with the homogenous model. Square pitch unit cell geometry was used in the calculations. In the bubble model, spherical and non-spherical bubbles at random positions, sizes and shapes were produced by Monte Carlo method. The results show that there are significant differences among the proposed models from the viewpoint of physical interaction mechanism. For the fully-developed bubbly flow, $k_{inf}$ is overestimated in the ring model by about $720{\pm}6pcm$ with respect to homogeneous model whereas underestimated in the bubble model by about $-65{\pm}9pcm$ with a standard deviation of 15 pcm. In addition, the ring model shows that the coolant must be separated into regions to properly represent the radial void distribution. Deviations in flux distributions principally occur in certain regions, such as corners. As a result, the bubble model in modeling the void fraction can be used in nuclear engineering calculations.

• 한국가시화정보학회지
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• 제14권2호
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• pp.52-60
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• 2016

The Passive Auxiliary Feedwater System(PAFS) is one of the advanced safety concepts adopted in the Advanced Power Reactor Plus(APR+). To validate the operational performance of the PAFS, detailed understanding of a boiling heat transfer on horizontal tube outside is of great importance. Especially, in the mechanistic boiling heat transfer model, it is important to visualize the phenomena but there are some limitations with conventional experimental approaches. In the present study, we devised a heater based on the Flexible Printed Circuit Board (FPCB) for a more comprehensive visualization and subsequently, a digital image processing technique for the bubble motion measurement was established. Using the measurement technique, important parameters of the nucleate boiling are analyzed.

• 대한기계학회논문집B
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• 제41권7호
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• pp.463-468
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• 2017

경피를 통한 약물 전달 방식에 있어, 본 연구에서 제안하고 있는 바늘 없는 주사기 시스템은 레이저와 마이크로젯 인젝터로 구성 되어 있다. 이때 마이크로젯 인젝터의 핵심 메커니즘은 레이저 유도버블이다. 동력원으로 Nd:YAG와 Er:YAG, 두 종류의 레이저가 사용되었다. 버블의 특성을 결정짓는 레이저 변수인 펄스폭, 파장 등이 본 연구에서 고려되었다. Nd:YAG 레이저의 경우에 펄스폭이 버블의 생존 시간보다 짧기 때문에 캐비테이션에 가까운 버블을 형성하는 반면 Er:YAG 레이저의 경우에 펄스폭이 상대적으로 길고 물에서의 흡수가 잘 되기 때문에 보일링 버블이 만들게 된다. 버블 및 마이크로젯의 자세한 움직임은 초고속 카메라를 통해 촬영되었다. 이와 같은 과정을 통하여 마이크로젯의 특성이 버블에 의해 결정되는 것을 본 연구를 통해 관찰되었다. 약물 전달 성능은 기니어피그 조직에 형광물질을 침투한 결과로 부터 분석하였다.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2771-2788
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• 2020

Experiments are conducted to study bubble flow behavior during the instability of subcooled boiling under uniform and non-uniform transverse heating. The non-uniform heat distribution introduces nonuniform bubble generation and condensation rates on the heated surface, which is different from the uniform heating. These bubble generation and condensation characteristics introduce a non-uniform local pressure distribution in the transverse direction, which creates an extra non-uniform pressure on the flowing bubbles. Therefore, different bubble flow behavior can be observed between uniform and non-uniform heating conditions. In the uniform heating, bubble velocity fluctuations are low, and the bubbles travel straight along the axial direction. In the non-uniform heating, more fluctuation in the bubble velocity occurs at low mass flow rate and high subcooled inlet temperatures, and reverse flow is observed. Additionally, the bubbles show a zigzag trajectory when they pass through the channel, which indicates the existence of cross flow in the transverse direction.